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Materials Science & Technology
The objectives of MSTD are: promote the advancement of materials science in Nuclear Science Technology; support the multidisciplines which constitute it; encourage research by providing a forum for the presentation, exchange, and documentation of relevant information; promote the interaction and communication among its members; and recognize and reward its members for significant contributions to the field of materials science in nuclear technology.
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2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott Downtown
Standards Program
The Standards Committee is responsible for the development and maintenance of voluntary consensus standards that address the design, analysis, and operation of components, systems, and facilities related to the application of nuclear science and technology. Find out What’s New, check out the Standards Store, or Get Involved today!
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Latest News
NWMO chooses vendors for Canadian repository
Canada’s Nuclear Waste Management Organization has selected five companies it is to work with to design and plan the organization’s proposed deep geologic repository for spent nuclear fuel. As the owner of the project, the NWMO will be working with WSP Canada, Peter Kiewit Sons (Kiewit), Hatch Ltd., Thyssen Mining Construction of Canada, and Kinectrics.
Fawzy Hammad Sallam, Eman Mohamed Ibrahim, Sayed Fahmy Hassan, A. Omar
Nuclear Technology | Volume 208 | Number 11 | November 2022 | Pages 1666-1680
Technical Paper | doi.org/10.1080/00295450.2022.2072650
Articles are hosted by Taylor and Francis Online.
The shielding characteristics of natural bentonite can be enhanced based on calcination and ball-milling processes for protection against gamma radiation. The calcination process increases the content of the oxide, which enhances the mass attenuation coefficient; however, the elimination of water and organic matter from bentonite clay structures increases the particle size, where large particle size has a negative effect on this mass attenuation coefficient. Therefore, the calcinated bentonite has been ball-milled to reduce the particle size and improve the attenuation properties of natural bentonite. Furthermore, the calcination process occurs at 700°C for 2 h because dehydration is completed above 500°C while dehydroxylation is observed at 700°C. Therefore, the shielding parameters have been determined for calcinated, ball-milled, pressed bentonite clay samples according to different gamma-ray energies (662, 1173, and 1332 keV), where the experimental setup is based on narrow beam transmission techniques with two sources (137Cs and 60Co). In addition, the particle size of bentonite clay has been characterized using X-ray diffraction patterns depending on two different methods: dynamic light scattering and Williamson-Hall size analyses. This study shows that the calcinated, ball-milled bentonite pressed at 150 bar has the highest linear and mass attenuation coefficients of μ = 0.13 cm−1 and μm = 0.082 cm2/gm, respectively. Moreover, the experimental and theoretical investigation of the mass attenuation coefficient is in good agreement.